| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A fuel depletion analysis of the MSRE and three conceptual small molten-salt reactors for Mo-99 production
|
Sheu, R.J.
|
|
2014
|
71 |
C |
p. 111-117
7 p.
|
artikel
|
| 2 |
Alternative off-site power supply improves nuclear power plant safety
|
Gjorgiev, Blaže
|
|
2014
|
71 |
C |
p. 304-312
9 p.
|
artikel
|
| 3 |
An assessment of prompt neutron reproduction time in a reflector dominated fast critical system: ELECTRA
|
Suvdantsetseg, E.
|
|
2014
|
71 |
C |
p. 159-165
7 p.
|
artikel
|
| 4 |
An evaluation on the cutting technologies for decommissioning of the large cylinder parts in the major components of NPPs
|
Jeong, KwanSeong
|
|
2014
|
71 |
C |
p. 340-342
3 p.
|
artikel
|
| 5 |
A new concept of Monte Carlo kinetics parameter calculation using complex-valued perturbation
|
Yamamoto, Toshihiro
|
|
2014
|
71 |
C |
p. 480-488
9 p.
|
artikel
|
| 6 |
A novel extension of chord length sampling method for TRISO-type fueled reactor applications
|
Liang, Chao
|
|
2014
|
71 |
C |
p. 440-450
11 p.
|
artikel
|
| 7 |
A simplified approach to evaluating severe accident source term for PWR
|
Huang, Gaofeng
|
|
2014
|
71 |
C |
p. 352-360
9 p.
|
artikel
|
| 8 |
Biogeochemical changes at early stage after the closure of radioactive waste geological repository in South Korea
|
Choung, Sungwook
|
|
2014
|
71 |
C |
p. 6-10
5 p.
|
artikel
|
| 9 |
Boiling heat transfer and dryout in helically coiled tubes under different pressure conditions
|
Chung, Young-Jong
|
|
2014
|
71 |
C |
p. 298-303
6 p.
|
artikel
|
| 10 |
Burnup estimation for plate type fuel assembly of research reactors through the least square fitting method
|
Alawneh, Luay M.
|
|
2014
|
71 |
C |
p. 37-45
9 p.
|
artikel
|
| 11 |
Calculation of radiation heat transfer view factors among fuel rod bundles based on CFD method
|
Yang, Lei
|
|
2014
|
71 |
C |
p. 462-466
5 p.
|
artikel
|
| 12 |
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics
|
Sartori, Alberto
|
|
2014
|
71 |
C |
p. 217-229
13 p.
|
artikel
|
| 13 |
Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casks
|
Kim, Hyungjin
|
|
2014
|
71 |
C |
p. 427-435
9 p.
|
artikel
|
| 14 |
Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarks
|
Calleja, M.
|
|
2014
|
71 |
C |
p. 145-158
14 p.
|
artikel
|
| 15 |
Design and analysis of operation performance of parameters of the integrated valve under the high temperature condition
|
Liu, Qian-feng
|
|
2014
|
71 |
C |
p. 237-244
8 p.
|
artikel
|
| 16 |
Design of a model predictive load-following controller by discrete optimization of control rod speed for PWRs
|
Kim, Jae Hwan
|
|
2014
|
71 |
C |
p. 343-351
9 p.
|
artikel
|
| 17 |
Development of a 1D transient electrorefiner model for pyroprocess simulation
|
Cumberland, Riley M.
|
|
2014
|
71 |
C |
p. 52-59
8 p.
|
artikel
|
| 18 |
Development of Monte Carlo-based pebble bed reactor fuel management code
|
Setiadipura, Topan
|
|
2014
|
71 |
C |
p. 313-321
9 p.
|
artikel
|
| 19 |
Development of the HELIOS/CAPP code system for the analysis of pebble type VHTR cores
|
Lee, Hyun Chul
|
|
2014
|
71 |
C |
p. 130-144
15 p.
|
artikel
|
| 20 |
Dynamic sequence analysis for feed-and-bleed operation in an OPR1000
|
Kim, Bo Gyung
|
|
2014
|
71 |
C |
p. 361-375
15 p.
|
artikel
|
| 21 |
Economic analysis of two nuclear fuel cycle options
|
Zhou, Chaoran
|
|
2014
|
71 |
C |
p. 230-236
7 p.
|
artikel
|
| 22 |
Editorial board
|
|
|
2014
|
71 |
C |
p. IFC-
1 p.
|
artikel
|
| 23 |
Effectiveness of source term optimization for higher disposal density of spent fuels in a deep geological repository
|
Cho, Dong-Keun
|
|
2014
|
71 |
C |
p. 125-129
5 p.
|
artikel
|
| 24 |
Evaluation of the performance of peridotite aggregates for radiation shielding concrete
|
Wang, Jinjun
|
|
2014
|
71 |
C |
p. 436-439
4 p.
|
artikel
|
| 25 |
Experimental and numerical testing of an innovative steam generator tube plugging procedure
|
Nicolici, S.
|
|
2014
|
71 |
C |
p. 190-197
8 p.
|
artikel
|
| 26 |
Experimental verification on the integrity and performance of the passive residual heat removal system for a SMART design with VISTA-ITL
|
Min, Byung-Yeon
|
|
2014
|
71 |
C |
p. 118-124
7 p.
|
artikel
|
| 27 |
Gamma and neutron attenuation behaviours of boron carbide–silicon carbide composites
|
Buyuk, Bulent
|
|
2014
|
71 |
C |
p. 46-51
6 p.
|
artikel
|
| 28 |
Goal-based angular adaptivity applied to the spherical harmonics discretisation of the neutral particle transport equation
|
Goffin, Mark A.
|
|
2014
|
71 |
C |
p. 60-80
21 p.
|
artikel
|
| 29 |
G4-STORK: A Geant4-based Monte Carlo reactor kinetics simulation code
|
Russell, Liam
|
|
2014
|
71 |
C |
p. 451-461
11 p.
|
artikel
|
| 30 |
Improvement on the calculation of D2O moderated critical systems with new thermal neutron scattering libraries
|
Márquez Damián, J.I.
|
|
2014
|
71 |
C |
p. 206-210
5 p.
|
artikel
|
| 31 |
Large scale applicability of a Fully Adaptive Non-Intrusive Spectral Projection technique: Sensitivity and uncertainty analysis of a transient
|
Perkó, Zoltán
|
|
2014
|
71 |
C |
p. 272-292
21 p.
|
artikel
|
| 32 |
Measurement of isothermal temperature reactivity coefficient at research reactor with IRT-4M fuel
|
Bily, Tomas
|
|
2014
|
71 |
C |
p. 91-96
6 p.
|
artikel
|
| 33 |
Monitoring and preventing numerical oscillations in 3D simulations with coupled Monte Carlo codes
|
Kotlyar, D.
|
|
2014
|
71 |
C |
p. 198-205
8 p.
|
artikel
|
| 34 |
Neutronic and thermal hydraulic analyses of LEU targets irradiated in a research reactor for Molybdenum-99 production
|
Jo, Daeseong
|
|
2014
|
71 |
C |
p. 467-474
8 p.
|
artikel
|
| 35 |
Numerical analysis of freezing controlled penetration behavior of the molten core debris in an instrument tube with MPS
|
Chen, Ronghua
|
|
2014
|
71 |
C |
p. 322-332
11 p.
|
artikel
|
| 36 |
Numerical modelling of low-Reynolds number direct contact condensation in a suppression pool test facility
|
Patel, G.
|
|
2014
|
71 |
C |
p. 376-387
12 p.
|
artikel
|
| 37 |
Numerical simulations of air–water cap-bubbly flows using two-group interfacial area transport equation
|
Wang, Xia
|
|
2014
|
71 |
C |
p. 399-410
12 p.
|
artikel
|
| 38 |
On an analytical representation for the solution of the neutron point kinetics equation free of stiffness
|
Wollmann da Silva, M.
|
|
2014
|
71 |
C |
p. 97-102
6 p.
|
artikel
|
| 39 |
On-line method to identify control rod drops in Pressurized Water Reactors
|
Souza, T.J.
|
|
2014
|
71 |
C |
p. 293-297
5 p.
|
artikel
|
| 40 |
On-the-fly sampling of temperature-dependent thermal neutron scattering data for Monte Carlo simulations
|
Pavlou, Andrew T.
|
|
2014
|
71 |
C |
p. 411-426
16 p.
|
artikel
|
| 41 |
Recommended dispersing conditions for broths used in the preparation of uranium microspheres with carbon
|
Hunt, R.D.
|
|
2014
|
71 |
C |
p. 1-5
5 p.
|
artikel
|
| 42 |
SAC-CFR computer code verification with Experimental Breeder Reactor II loss-of-primary-flow-without-scram tests data
|
Guo, Chao
|
|
2014
|
71 |
C |
p. 166-173
8 p.
|
artikel
|
| 43 |
Sensitivity analysis of CHF parameters under flow instability by using a neural network method
|
Li, Jingjing
|
|
2014
|
71 |
C |
p. 211-216
6 p.
|
artikel
|
| 44 |
Stability improvement of noise analysis method in the case of random noise contamination for subcriticality measurements
|
Kong, Chidong
|
|
2014
|
71 |
C |
p. 245-253
9 p.
|
artikel
|
| 45 |
Technical design and engineering prototype experiment of active magnetic bearing for helium blower of HTR-PM
|
Yang, Guojun
|
|
2014
|
71 |
C |
p. 103-110
8 p.
|
artikel
|
| 46 |
The ADOPT code for automated fast reactor core design
|
Qvist, Staffan
|
|
2014
|
71 |
C |
p. 23-36
14 p.
|
artikel
|
| 47 |
The complex nonlinear dynamics in the multiple boiling channels coupling with multi-point reactors with constant total flow rate
|
Lee, Jin Der
|
|
2014
|
71 |
C |
p. 174-189
16 p.
|
artikel
|
| 48 |
The max–min ant system and tabu search for pressurized water reactor loading pattern design
|
Lin, Chaung
|
|
2014
|
71 |
C |
p. 388-398
11 p.
|
artikel
|
| 49 |
Thermal analysis of prismatic gas-cooled reactor core under coolant channel blockage accidents
|
Lee, Sung Nam
|
|
2014
|
71 |
C |
p. 11-22
12 p.
|
artikel
|
| 50 |
The scenario-based system of workers training to prevent accidents during decommissioning of nuclear facilities
|
Jeong, KwanSeong
|
|
2014
|
71 |
C |
p. 475-479
5 p.
|
artikel
|
| 51 |
Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model
|
Lee, Yoonhee
|
|
2014
|
71 |
C |
p. 254-271
18 p.
|
artikel
|
| 52 |
UWB1 – Fast nuclear fuel depletion code
|
Lovecký, M.
|
|
2014
|
71 |
C |
p. 333-339
7 p.
|
artikel
|
| 53 |
Verification of the BISON fuel performance code
|
Hales, J.D.
|
|
2014
|
71 |
C |
p. 81-90
10 p.
|
artikel
|
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